ML20045E039

Proposed TS 5.3.1 Re Requirements for Fuel Assemblies to Provide Flexibility in Repair of Fuel Assemblies Containing Damaged & Leaking Fuel Rods by Reconstituting Assemblies

ML20045E039
Person / Time
Site:	Catawba
Issue date:	06/17/1993
From:	DUKE POWER CO.
To:
Shared Package
ML20045E037	List: ML20045E036 ML20045E039
References
NUDOCS 9307010017
Download: ML20045E039 (3)

Text

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ATTACHMENT II DUKE POWER COMPANY.

CATAWBA NUCLEAR STATION PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS l

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l DESIGN FEATURES j

DESIGN PRESSURE AND TEMPERATURE ( -

5.2.2 The reactor containment vessel is designed and shall be maintained for a maximum internal pressure of 15 psig and a temperature of 328 F.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly nominally containing 264 fuel rods clad with Zircaloy-4, except that substitu- g C6 tions of fuel rods by filler rods consisting of Zircaloy-4 or stainless steel, W'b '

or by vacancies, may be made in fuel assemblies if justified by cycle-specific reload analyses using NRC-approved methodology. Should more than 30 rods in the core, or 10 rods in any assembly, be replaced per refueling, a special g4g; l

report describing the number of rods replaced will be submitted to the Commis-sion pursuant to Specification 6.9.2 within 30 days after cycle startup. Each fuel rod shall have a nominal active fuel length of 144 inches. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.0 weight percent U-235 with a maximum enrichment tolerance of i 0.05 weight percent U-235.

CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 53 full-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber ma.terial of which 102 inches shall be 100% boron carbide and remaining 40-inch g tip shall be 80% silver, 15% indium, and 5% cadmium. (

For Units 1 and 2, all control rods shall be clad with stainless steel tubing, except for Unit 2, a maximum of one Rod Cluster Contr'ol Assembly may have Inconel clad control rods.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:

a. In accordance with the Code requirements specified in Section 5.?

of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements,

b. For a pressure of 2485 psig, and

c. For a temperature of 650 F, except for the pressurizer which is  ;

680 F.

VOLUME 5.4.2 The tot-i water and steam volume of the Reactor Coolant System is 12,040 1 100 cubic feet at a nominal T avg f 525*F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown in Figure 5.1-1. (

CATAWBA - UNITS 1 & 2 5-6 Amendment No d unit 1)  !

Amendment No. M unit 2) l 1

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The reactor shall contain Ict3 fuel assemblies. Each assembly shall censist of a matrix o'f zircaloy clad fuel rods with an. initial composition of natural or slightly enriched. uranium dioxide as. fuel material.

Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configura-tions, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applica-ble NRC staff-approved codes and methods, and shown by tests or analyses to' comply with all fuel safety design

-bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.

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